ML20040B984

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Notifies That 810714 Response to 791120 Request for Addl Info Re Containment & Shielding Issues Is Inadequate. Evaluations Concerning Performance at Normal for Containment Vessels & Gamma Shield Design Requested
ML20040B984
Person / Time
Site: 07109851
Issue date: 01/12/1981
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To: Ross D
ENERGY, DEPT. OF
References
NUDOCS 8201270136
Download: ML20040B984 (2)


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U.S. Department of Energy

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ATTN: Dr. Donald M. Ross J

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Gentlemen:

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This refers to our raview of your Safety Analysis Report for Packaging (SARP) for the Model fic. Lithium Hydroxide Fire and Impact Shield package, submitted by letter dated July 31, 1978. We have reviewed your July 14, 1981 response to our Novembe-20, 1979 request for additional information needed to review this package. We find that your response is inadequate with respect to the basic issues of containment and shielding addressed in our request. We note that two items have been satisfied, a drawing has been provided for the inner container gamma shield, and the requirements of 10 CFR 571.42 are no longer applicable since plutonium is not to be shipped. The remaining items should be addressed and resubmitted, subject to the comments provided below.

To evaluate the performance'of normal form containment vessels it is necessary to establish a criteria for containment. Each containment vessel to be used should be identified, and important features defined.

Containment vessels must be shown to meet the established containment criteria for test conditions defined in 10 CFR Part 71, and they must have a specified test program to ensure continued' compliance with the established containment criteris while in use (i.e., specified leak tests should satisfy the containment criteria).

In order to show conpliance of the requirements of 71.35(a) and 71.36(gama shield design to the shielding b) it is necessary to evaluate the effects of normal and accident conditions of 10 CFR Part 71 on the gamma shield. The evaluation can be based on test, analysis, etc., but must.

be done to demonstrate that :hielding effectiveness is not significantly

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NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY g

U.S. Department of Energy JAN 121982

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Please advise us within thirty (30) days from the date of this letter

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when the above infonation will be provided.

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Sincerely, F

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l Charles E. MacDonald, Chief Transportation Certification Branch i

Division of Fuel Cycle and Material Safety, NMSS cc: DOE, Oak Ridge Operations Office ATTN: Mr. William H. Travis P.O. Box E~

Oak Ridge, TN 37830 l

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